Oral Program - elsevier.com · Armstrong, A.J. Wilkinson, University of Oxford, UK [O4.02] Phosphorous effect on vacancy-mediated diffusion and ordering kinetics in nickel alloys

The 5th Nuclear Materials Conference 2018

Oral Program

Sunday 14th October 2018 17:00-18:00 Registration

Room: Emerald Foyer

Monday 15th October 2018 07:30-08:45 Registration

Room: Emerald Foyer

08:45-08:55 Welcome and Introductions | Room: Seattle 1-3

08:55-09:15 Welcome | Room: Seattle 1-3

09:15-09:30 Introduction | Room: Seattle 1-3

09:30-10:10

Robert Cahn Award Lecture |Room: Seattle 1-3

[L01]

Radioactive waste forms for the future

R.C. Ewing, Stanford University, USA

10:10-10:30 Coffee Break | Room: Emerald

10:30-11:10 Room: Seattle 1-3

[PS01]

New insights from advanced characterization of irradiated fuels

J. Bertsch*1, M. Martin1, M. Chollet1, D. Grolimund2, G. Kuri1, 1Nuclear Energy and Safety, Switzerland, 2Swiss Light Source, Switzerland

11:10-11:50 [PS02]

Behavior of accident tolerant fuel cladding materials during severe accidents

M.K. Grosse*, M. Steinbrück, J. Stuckert, C. Tang, Karlsruhe Institute of Technology, Germany

11:50-13:00 Lunch Break Room: Emerald

Room: Seattle 1 Room: Seattle 2 Room: Seattle 3 Room: Belltown Room: Pioneer Room: Capitol Hill

13:00-15:15 Track 2- Structural and

Functional Materials for

Fission and Fusion

reactors

Session Chairs:

M.G. Burke, K. Field,

S. Kondo

Track 4- Modelling and

Simulation of Structural

Materials

Session Chairs: B. Wirth,

T. Okita, M. Gilbert

Track 7- Characterization

of Irradiated Materials and

Nuclear Fuels

Session Chairs: R.

Kennedy, J. Wharry


Simulation of Nuclear

Fuels

Session Chair: G. Pastore

Track 5- Behavior of

Materials during Severe

Accidents and

Accident Tolerant Fuels

Session Chair: M. Kurata

Track 8- Materials for the

Nuclear Fuel Cycle

Session Chairs: C. Fazio,

S. Miro, K. Minato

13:00-13:25

[O2.01]

The transformational

challenge reactor

K.A. Terrani, Oak Ridge

National Laboratory,

USA

[O4.01]

Multi-scale simulation for

reduced activation

ferritic/martensitic steel

with dislocation based

constitutive model

W. Jeong1 ,3, Y.E. Na2, D.

Jang2, M.G. Lee*3, 1Korea

University, Republic of

Korea, 2KAIST, Republic of

Korea, 3Seoul National


Korea

[O7.01]

Overview of the U.S.

Nuclear Science User

Facilities (NSUF)

J.R. Kennedy, Idaho

National Laboratory, USA

[O3.01]

UO2 fuel oxidation,

oxygen redistribution, and

fission gas release from

UO2+x

L-O. Jernkvist, A.R.

Massih*, Quantum

Technologies AB, Sweden

[O5.01]

Developing the test

conditions for the first

fuelled transients in the

TREAT reactor

D. Kamerman*, N.

Woolstenhulme, C. Jensen,

C. Davis, C. Folsom, D.

Wachs, Idaho National

Laboratory, USA

[O8.01]

Investigating hydrogen

segregation to secondary

phase particles in

Zircaloy-2 and Zircaloy-4

fuel cladding using

nanoscale secondary ion

mass spectroscopy

C. Jones*1, M. Preuss1, K.

Moore1 ,2, 1University of

Manchester, UK,

2University of Manchester,

UK, 3Wood plc, UK


Track 2- Structural and


Fission and Fusion

reactors

Session Chairs: M.G.

Burke, K. Field, S.

Kondo



Materials

Session Chairs: B. Wirth, T.

Okita, M. Gilbert



Nuclear Fuels

Session Chairs: R.

Kennedy, J. Wharry



Fuels




Accidents and




Nuclear Fuel Cycle


S. Miro, K. Minato

13:25-13:50 [O2.02]

Radiation resistant high

entropy alloys for fast

reactor cladding

applications

A. Kareer*, D.E.J.

Armstrong, A.J.

Wilkinson, University of

Oxford, UK

[O4.02]

Phosphorous effect on

vacancy-mediated

diffusion and ordering

kinetics in nickel alloys

J.H. Ke*, G. Young, J.

Tucker, Oregon State

University, USA

[O7.02]

The influence of post-

irradiation annealing on

the crack growth

resistance of Zr-2.5Nb

S. St Lawrence, Canadian

Nuclear Laboratories,

Canada

[O3.02]

Modeling volatile fission

products transport into the

germinal v2 fuel

performance code by

coupling to

thermochemical software

J-C. Dumas*1, M. Lainet1,

K. Samuelsson2, B.

Sundman3, 1CEA,

DEN/DEC/SESC, France,

2KTH, Sweden, 3INSTN,

France

[O5.02]

Fission products and

nuclear fuel behaviour

under severe accident

conditions: Speciation of

fission products in the

Verdon 3 and -4 samples

F. Audubert*, C. Le Gall, L.

Fayette, P. Bienvenu, I.

Zacharie-Aubrun, K. Hanifi,

Y. Pontillon, CEA, France

[O8.02]

Zirconium hydride

nucleation and growth

kinetics studied using

differential scanning

calorimetry and

synchrotron radiation

diffraction

E. Lacroix*, A.T.

Motta, Pennsylvania

State University, USA

13:50-14:15 [O2.03] Designing solute

stabilized nanocrystalline

tungsten alloys for fusion

applications

J.R. Trelewicz, Stony

Brook University, USA

[O4.03]

Simulation of irradiation-

induced grain boundary

phosphorus segregation

by first-principles-based

rate theory model

including trapping and

detrapping processes

K. Ebihara*, T. Suzudo, M.

Yamaguchi, Japan

Atomic Energy Agency,

Japan

[O7.03]

Microstructural

investigation of hydride

reorientation in zirconium

based spent nuclear fuel

cladding

T.S. Smith*1, S. Zinkle1, K.

Terrani2, 1The University of

Tennessee Knoxville, USA,

2Oak Ridge National

Laboratory, USA

[O3.03]

Modeling ATF with coated

cladding under accident

conditions using BISON

code

W. Liu*, A. Mai, J.

Rashid, Structural Integrity

Associates, Inc, USA

[O5.03]

Modelling of Cs

chemisorption behaviour

under LWR severe accident

S. Nishioka*1 ,2, K.

Nakajima1 ,2, E. Suzuki1, F.

Miradji1 ,2, M. Osaka1

,2, 1Japan Atomic Energy

Agency, Japan,

2International Research

Institute for Nuclear

Decommissioning, Japan

[O8.03]

Comparison of second

phase particles in

autoclave and neutron

irradiated Zr cladding

alloys

J. Hu*, S. Lozano-Perez, M.

Moody, C.

Grovenor, University of

Oxford, UK

14:15-14:40 [O2.04]

Pure vanadium

characterization for

fusion applications

B. Garcinuño*1 ,2, M.

Malo1, H. Liu3, I.

Fernández-Berceruelo1,

D. Rapisarda1, H. Zhou3,

G. Luo3, J.

Sanz2, 1CIEMAT, Spain,

2UNED, Spain, 3ASIPP,

China

[O4.04]

Ab initio study of point

defect interactions with

grain boundaries in fcc

nickel

E. Toijer*1, N. Sandberg1 ,2,

P. Olsson1, 1KTH Royal

Instiute of Technology,

Sweden, 2OECD-NEA

Boulogne Billancourt,

France

[O7.04]

The effect of transverse

and axial cold work on

irradiation creep of

Zircaloy-2 alloys at low

(330 K) temperature

X. Song*, W. Li, Canadian


Canada

[O3.04]

Validation of the pre-

transient metal fuel

performance models of

SAS4A A. Karahan, Argonne


[O5.04]

ATTILHA - A novel

experimental setup for

thermodynamic and

thermophysical properties

measurements on nuclear

materials

A. Quaini*, S. Gossé, C.

Guéneau, T. Alpettaz, E.

Lizon a Lugrin, C.

Bonnet, Université Paris-

Saclay, France

[O8.04]

Hydrogen migration in

duplex zirconium fuel

cladding quantified by

high-resolution neutron

imaging

W. Gong*1, P. Trtik1, L.

Duarte1, M. Mille1,2, J.

Bertsch1 1Paul Scherrer Institut,

Switzerland, 2EPF

Graduate School of

Engineering, France




Fission and Fusion

reactors Session Chairs: M.G.

Burke, K. Field, S.

Kondo



Materials Session Chairs:

B. Wirth, T. Okita,

M. Gilbert



Nuclear Fuels

Session Chairs:

R. Kennedy, J. Wharry



Fuels




Accidents and




Nuclear Fuel Cycle


S. Miro, K. Minato

14:40-15:15 [T2.INV01]

Structural materials

roadmap for the Fluoride-

Salt-Cooled High

Temperature Reactor

(FHR)

M. Hackett, Kairos

Power, LLC, USA

[T4.INV01]

Combined analysis of

first-principles

calculations and fracture

mechanics experiments

on intergranular

embrittlement of a Ni-Cr

steel

M. Yamaguchi, Japan


Japan

[T7.INV01]

Understanding

irradiation-induced

growth of Zr-based

fuel cladding through

advanced

characterisation

M. Preuss, University

of Manchester, UK

[T3.INV01]

Insight into the behaviour

of nuclear fuels through

investigations coupling

multi-scale modelling and

separate effects

experiments

G. Jomard*1, M-F. Barthe2,

R. Belin1, M. Bertolus1, E.

Bourasseau1, G. Carlot1, I.

Cheik Njifon1, M. Freyss1,

M. Gérardin1, S.

Maillard1, 1CEA/DEN,

France, 2CNRS/CEMHTI,

France

[T5.INV01]

Outline of a project for

core/plant status

evaluation of Fukushima-

Daiichi units 1 to 3 I. Sato*1 ,6, S. Mizokami1 ,6,

M. Kurata1 ,6, K. Okamoto1

,6, T. Yamashita1 ,6, T.

Honda2 ,6, K. Ito2 ,6, K.

Nozaki2 ,6, M. Pellegrini3, M.

Naito3, 1JAEA, Japan,

2TEPCO, Japan, 3IAE,

Japan, 4Toshiba ESS,

Japan, 5Hitachi-GE, Japan,

6IRID, Japan

[T8.INV01]

Process development of

ferritic steels for high dose

fast reactor applications

S.A. Maloy*1, E. Aydogan1,

B. Eftink1, T.A. Saleh1, T.J.

Lienert1, M. Toloczko2, T.S.

Byun2, C. Lavender2, G.R.

Odette3, M.E. Alam3, 1Los

Alamos National

Laboratory, USA, 2Pacific

Northwest National

Laboratory, USA,

3University of California,

Santa Barbara, USA, 4Oak

Ridge National

Laboratory, USA, 5CEA

Saclay, France

15:15-15:45 Coffee Break Room: Emerald



Fission and Fusion

reactors Room: Seattle 1

Session Chairs: S. Kondo,

A. Kimura



Materials

Room: Seattle 2


Okita, M. Gilbert



Nuclear Fuels

Room: Seattle 3

Session Chairs: R.

Kennedy, J. Wharry

Track 3- Modelling and Simulation of Nuclear Fuels

Room: Belltown

Session Chair: A. Prudil



Accidents and Accident

Tolerant Fuels

Room: Pioneer

Session Chair: I. Sato


Nuclear Fuel Cycle

Room: Capitol Hill


S. Miro, K. Minato

15:45-16:10 [O2.05]

Understanding neutron

irradiation performance

of dense γ-LiAlO2

D.J. Senor*, D.E.

Burkes, Pacific

Northwest National

Laboratory, USA

[T4.INV04]

Free energy landscape of

point defects in body-

centered-cubic metals

C.M. Marinica, Commissariat à l'énergie

atomique et aux énergies

alternatives , France

[O7.05]

Investigation on

(U,Pu)O2 fuel

microstructure by

Raman microscopy

L. Medyk1, P. Simon2, A.

Canizares2, D. Manara4,

R.J.M. Konings4, J-Y.

Colle4, C. Valot1, G.

Montagnac3, P.M.

Martin*1, 1CEA, France,

2CNRS Orléans, France,

3CNRS, ENS Lyon,

France, 4JRC-Karlsruhe,

[O3.05]

Developments in

engineering-scale

modelling of pore

migration in oxide fuels at

high temperature

S.R. Novascone*1, T.

Ozawa2, P.G. Medvedev1,

S. Hirooka2, 1Idaho

National Laboratory, USA,

2Japan Atomic Energy

Agency, Japan

[O5.05]

Thermophysical

property measurements

of molten stainless steel

containing 10mas%-B4C

by electromagnetic

levitation technique

H. Fukuyama*1, H.

Higashi1, H.

Yamano2, 1Tohoku

University, Japan,


Agency, Japan

[O8.05]

Fabrication and thermal

properties of sol-gel

derived enhanced UO2

ceramic fuel candidates

S.C. Finkeldei*, J.O.

Kiggans, R.D. Hunt, K.A.

Terrani, A.T. Nelson, Oak

Ridge National

Laboratory, USA


Germany



Fission and Fusion


Burke, K. Field, S.

Kondo



Materials Session Chairs: B. Wirth,




Nuclear Fuels

Session Chairs: R.

Kennedy, J. Wharry



Fuels Session Chair: G. Pastore



Accidents and




Nuclear Fuel Cycle


S. Miro, K. Minato

16:10-16:35 [O2.06]

Investigation of

alumina coating as

tritium permeation

barrier for molten salt

nuclear reactors

G. Zheng*, D.

Carpenter, Massachus

etts Institute of

Technology, USA

[O4.05]

Modelling the effect of iodine at stress corrosion crack tips in zirconium using hybrid quantum mechanics/molecular dynamics simulations

V. Podgurschi*1, J.R. Kermode2, M.R. Wenman1, 1Imperial College London, UK, 2University of Warwick, UK

[O7.06]

Evaluation of radiation

damage of uranium-

molybdenum alloys

using extended X-ray

absorption fine structure

and synchrotron X-ray

diffraction

G. Park1, K. Bemis1, R.

Seibert2, D. Velazquez2,

J. Terry2, J. Wright3, D.

Sprouster4, M.

Elbakhshwan4, L. Ecker4,

M.

Okuniewski*1, 1Purdue

University, USA, 2Illinois

Institute of Technology,

USA, 3Argonne National

Laboratory, USA,

4Brookhaven National

Laboratory, USA

[O3.06]

Neutronic assessment of a

small-scale fuel irradiation

experiment in the High

Flux Isotope Reactor (HFIR)

J.R. Burns*, C.M. Petrie, R.

Morris, K.A. Terrani, Oak

Ridge National Laboratory,

USA

[O5.06]

Thermal and mechanical

properties of Fe2Zr: Main

component of the metallic

phase of fuel debris

D. Okada*1, H. Ishii1, Y.

Takamatsu1, Y. Ohishi1, H.

Muta1, K. Kurosaki1

,2, 1Osaka University,

Japan, 2University of Fukui,

Japan, 3JST, Japan

[O8.06]

Development of a high

temperature ultrasonic

viscometer for molten salt

S. Mastromarino*1 ,2, M.

Rohde1, O. Benes2, J.L.

Kloosterman1, 1Delft

University of Technology,

The Netherlands,

2European Commission,

Germany

16:35-17:00 [O2.07]

Static and impact

fracture characteristics

of cast austenitic

stainless steels after

long-term thermal aging

T.S. Byun*, D.A. Collins,

T.G. Lach, K.

Kruska, Pacific

Northwest National

Laboratory, USA

[O4.06]

Microstructural modeling of

concrete in LWR with

MOSAIC

J.D. Arregui-Mena*1,

A.B. Giorla1, G.E.

Jellison1, E. Tajuelo-

Rodriguez1, C.E.

Torrence2, Y. Le Pape1,

T.M. Rosseel1, 1Oak

Ridge National

Laboratory, USA,

2Texas A&M University,

USA

[O7.07]

Measurements of acoustic

phonons in irradiated UO2

epitaxial films

S. Rennie*1, E. Lawrence

Bright1, J.E. Darnbrough2 ,1,

L. Paolasini3, A. Bosak3,

G.H. Lander4, R.

Springell1, 1University of

Bristol, UK, 2University of

Oxford, UK, 3ESRF, France,


Joint Research Centre,

Germany

[O3.07]

Mechanical property

evolution with radiation

damage in (U,Pu)O2: A MD

simulation study

L. Van Brutzel*1, H. Balboa-

Lopez1, A. Chartier1, Y. Le

Bouar2, 1CEA, France,

2CNRS, France

[O5.07]

Modeling high-

temperature corrosion of

zirconium alloys fuel

cladding using XFEM with

BISON

L. Borrel1, W. Jiang2, B.W.

Spencer2, K. Shirvan3, A.

Couet*1, 1University of

Wisconsin-Madison, USA,

2Idaho National

Laboratory, USA,

3Massachusetts Institute of

Technology, USA

[O8.07]

Impact of lanthanide

elements on the

dissolution of uranium

dioxide

T. Cordara1, L.

Claparede1, S. Szenknect1,

A. Mesbah1, C. Lavalette2,

R. Podor1, N.

Dacheux*1, 1University

Montpellier, France,

2AREVA NC, France

17:00-17:25 [O2.08]

Co-dependent

microstructural

evolution pathways in

ferrite and at ferrite-

austenite phase

boundary in cast

[O7.08]

Synergetic effect of ballistic

damage and electronic

excitations in uranium

dioxide investigated by in-

situ Raman spectroscopy

G. Gutierrez*1, M. Bricout1, C.

17:15-

17:50 [T3.INV02]

Multiscale

modeling of fission

gas bubble

evolution in UO2

under nominal

operating

17:15-

17:50 [T5.INV02]

A modern

methodology for

fuel safety

research

D. Wachs*, C.

Jensen, N.

[O8.08]

Layered double

hydroxides synthesis and

application for radioactive

iodine removal

W. Um*, J. Kang, Pohang

University of Science and


Tuesday 16th October 2018

08:30-09:10 Room: Seattle 1-3

[PS03]

Challenges in predicting irradiated nuclear fuel thermodynamics

C. Guéneau, Commissariat à l'énergie atomique et aux énergies alternatives, France

09:10-09:50 [PS04]

Improving atomic displacement calculations with physically realistic damage models: arc-dpa and rpa

K. Nordlund, University of Helsinki, Finland


Room: Seattle 1 Room: Seattle 2 Room: Seattle 3 Room: Belltown Room: Pioneer Room: Capitol Hill



Fission and Fusion

reactors


Burke, M. Hackett



Materials





Nuclear Fuels

Session Chairs: F. Cappia,

T. Wiss,


Simulation of Nuclear Fuels

Session Chair: A. Prudil




Tolerant Fuels

Session Chair: A. Nelson


Nuclear Fuel Cycle

Session Chairs:

C. Fazio, S. Miro, K.

Minato

10:20-10:45 [O2.09]

Thermogravimetric

oxidation analysis of

carbon tokamak

dust and flakes

U. Shahid1, B.W.N.

Fitzpatrick*1, J.W.

Davis2, M.H.A.

Piro1, 1University of

Ontario Institute of

Technology,

Canada, 2University

of Toronto, Canada

[O4.07]

A microstructure dependent

rate theory for predicting

defect evolution in

irradiated polycrystalline

LiAlO2

S.Y. Hu*, Y.L. Li, D.E. Burkes,

D.J. Senor, Pacific

Northwest National

Laboratory, USA

[O7.09]

Recent observations from

the microstructural

characterization of

irradiated U-Mo fuels

using advanced

techniques

D. Keiser*, B. Miller, J.

Gan, L. He, D. Jadernas,

M. Bachhav, A. Robinson,

J. Madden, Idaho


[O3.08]

Evaluation of explicit

fracture models on the

performance of FeCrAl and

Zircaloy cladding using the

BISON fuel performance

code

R.T. Sweet*1, Y.R. Rashid2,

B.D. Wirth1, 1University of

Tennessee, USA, 2Structural

Integrity Associates Inc.,

USA

[O5.08]

Accident tolerant FeCrAl-

ODS ferritic steels in Japan:

High temperature steam

oxidation and creep rupture

strength

S. Ukai*1, T. Sowa1, S.M.S.

Aghamiri1, N. Sugawara1, S.

Zhang1, N. Oono1, S.

Hayashi1, K. Sakamoto2, T.

Furukawa3, 1Hokkaido

University, Japan, 2Nippon

Nuclear fuel Development

[O8.09]

Effect of platinoid

elements on the

dissolution of uranium

dioxide

T. Cordara1, S.

Szenknect1, L.

Claparede1, A. Mesbah1,

C. Lavalette2, R. Podor1,

N. Dacheux*1, 1University

Montpellier, France,

2AREVA NC, France

austenitic stainless

steels during thermal

aging

T.G. Lach*, A. Devaraj,

T.S. Byun, Pacific

Northwest National

Laboratory, USA

Onofri1, F. Lepretre1, R. Belin1,

L. Thomé2, A. Debelle1 ,2, F.

Garrido2, 1CEA, France,

2Centre de Sciences

Nucléaires et de Sciences

de la Matière, France

conditions

B.D. Wirth*1 ,2, A.D.

Andersson3, S.

Blondel1, G.

Pastore4, R.J. Kurtz5,

W.

Setyawan5, 1Univer

sity of Tennessee,

USA, 2Oak Ridge

National

Laboratory, USA,

3Los Alamos

National

Laboratory, USA,

4Idaho National

Laboratory, USA,

5Pacific Northwest

National

Laboratory, USA

Woolstenhulme, I

daho National

Laboratory, USA

Technology (POSTECH),

Republic of Korea

17:25-19:10 Poster Session 1 & Drinks Reception


Co. Ltd., Japan, 3Japan


Japan



Fission and Fusion

reactors


Burke, M. Hackett



Materials


Okita, M. Gilbert



Nuclear Fuels

Session Chairs: F. Cappia,

T. Wiss



Session Chair:

A. Prudil




Tolerant Fuels



Nuclear Fuel Cycle

Session Chairs:

C. Fazio, S. Miro, K.

Minato

10:45-11:10 [O2.10]

Corrosion of

structural materials

in molten chloride

salts

S.S. Raiman*1, J.W.

McMurray1, R.T.

Mayes1, J.M. Kurley1,

J. Moon2 ,1, 1Oak

Ridge National

Laboratory, USA,

2University of

California, USA

[O4.08]

Effect of

trapping/detrapping SIA

clusters by impurities on

damage accumulation in

neutron irradiated tungsten:

Comparison of 14 MeV-

neutron and High-Flux

Isotope Reactor (HFIR) PKA

spectra

G. Nandipati*1, W.

Setyawan1, K.J. Roche1 ,3,

R.J. Kurtz1, B.D.

Wirth2, 1Pacific Northwest


2University of Tennessee,

USA, 3University of

Washington, USA

[O7.10]

Examination of UO2

surface oxidation using

atomic-scale electron

energy loss spectroscopy

S.R. Spurgeon*1, M. Sassi1,

J. Stubbs2, E. Ilton1, E.

Buck1, 1Pacific Northwest


2University of Chicago,

USA

[O3.09]

Modelling the effect of

fracture strength on pellet

fracture patterns in

peridynamics

L. Jones*, T.A. Haynes, M.R.

Wenman, Imperial College

London, UK

[O5.09]

Oxidation behaviour of

alumina-forming duplex

stainless steels in high

temperature steam

environments

H. Kim*, C. Kim, C.

Jang, Korea Advanced

Institute of Science and

Technology, Republic of

Korea

[O8.10]

Sequestration of

radionuclides in metal-

organic frameworks from

first principles

calculations

S. Pendey1, Z. Jia1, B.

Demaske1, N. Shustova2,

E. Dolgopolova2, W.

Setyawan3, C.H.

Henager3, S.R.

Phillpot*1, 1University of

Florida, USA, 2University of

South Carolina, USA,

3Pacific Northwest


11:10-11:35 [O2.11]

A combined

corrosion/irradiation in

situ material testing

facility for molten salt

reactor materials

W. Zhou*, M.P.

Short, Massachusetts


USA

[O4.09]

Interactions between

transmutation Re and

irradiation defects in W bulk

by molecular dynamics

simulations based on new W-

Re potentials

Y.C. Chen*1, H.Q. Deng1, J.

Fu1, L.X. Liu1, W.Y. Hu1, F. Gao1

,2, 1Hunan University, China,

2University of Michigan, USA

[O7.11]

Preliminary

postirradiation

examination of several

EBR-II metallic fuel

pins

L.C. Capriotti*, J.H.

Harp, D.W. Wachs, S.H.

Hayes, Idaho National

Laboratory, USA

[O3.10]

Predicting the

behaviour of

complex grain

boundaries in

zirconia to

understand cladding

corrosion and PCI

M.J.D. Rushton*1,

W.E. Lee1 ,2, S.C.

Middleburgh1, 1Ban

gor University, UK,

2Imperial College

London, UK

[O5.10]

Tritium permeation through

oxide film of FeCrAl-ODS

ferritic steel

K. Sakamoto*1, Y. Urabe2, K.

Hashizume2, S.

Yamashita3, 1NFD, Japan,

2Kyushu University, Japan,

3JAEA, Japan

[O8.11]

Recent structural

investigations of zirconium-

plutonium molybdate

precipitation and its

inhibition during the

dissolution step of the spent

nuclear fuels treatment

S. Costenoble*1, M.

Nadolny2, N. Henry3, T.

Dumas1, C. Lavalette2, M.

Rivenet3, S.

Grandjean1, 1CEA, France,

2Orano Group, France,

3UCCS, France

11:35-12:00 [O2.12]

Corrosion of Hastelloy-n

in molten FLiNaK salt at

700°C

C. Falconer*1, W.H.

Doniger1, R. Scarlat1, L.

Shao2, K. Sridharan1, A.

Couet1, 1University of

[O4.10]

First-principle study of H in

Fe/W interface

J.M. Shi*, N.

Hashimoto, Hokkaido

University, Japan

[O7.12]

Postirradiation examination

of recently irradiated

metallic fuel concepts

J.M. Harp*, L. Capriotti, F.

Cappia, Idaho National

Laboratory, USA

[O3.11]

Simulation of historical

experiments related to

hydrogen migration and

redistribution in Bison

Z. Aly*1, G. Pastore2, N.

Brown1, A.

Casagranda2, 1Pennsylvania

[O5.11]

The solubility of hydrogen in

U3Si2 accident tolerant fuel

candidate - impact on fuel

manufacturing and

operation

S.C. Middleburgh*1 ,2, A.

Claisse2, D.A. Andersson3,

[O8.12]

Iron XANES analysis of

irradiated Zircaloy-4 oxide

layers formed at different

neutron flux levels and

corrosion temperatures

B. Ensor*1, J.R.




USA

State University, USA, 2Idaho


R.W. Grimes4, P. Olsson5, S.

Mašková6, 1Bangor

University, UK,

2Westinghouse Electric

Sweden AB, Sweden, 3Los

Alamos National

Laboratory, USA, 4Imperial

College London, UK, 5KTH,

Sweden, 6Charles University,

Czech Republic

Seidensticker1, A.T.

Motta2, 1Naval Nuclear

Laboratory, USA, 2The

Pennsylvania State

University, USA



Fission and Fusion


Burke, M. Hackett



Materials

Session Chair: B. Wirth, T.

Okita, M. Gilbert



Nuclear Fuels Session Chair: F. Cappia, T.

Wiss



Session Chair:

A. Prudil




Tolerant Fuels



Nuclear Fuel Cycle

Session Chair: C. Fazio,

S. Miro, K. Minato

12:00-12:25 [O2.13]

Corrosion behavior of Ni-

based alloy in molten

FLiNaK salt as a

fundamental research

on molten salt reactors

K. Ogasawara*1, Y.

Sekiguchi1, T. Terai1, H.

Kawamura2, K. Tsuchiya3,

T.Watanabe4, 1University of Tokyo,

Japan, 2Chiyoda

Technol Corp., Japan,


Agency, Japan, 4ational

Institute for Fusion

Science, Japan

[O4.11]

Modeling ductile-phase

toughened tungsten for

plasma-facing materials by

a multiscale microstructural

approach

B.N. Nguyen*, C.H. Henager,

Jr., R.J. Kurtz, Pacific

Northwest National

Laboratory, USA

[O7.13]

Microstructural evolution

and phase

transformations in U-10Mo

alloys with varying Zr

content after heat

treatments relevant to the

monolithic fuel plate

fabrication process

A. Mehta1, N. Eriksson1, R.

Newell1, L. Zhou1, E. Schulz1,

W. Sprowes1, F. Betancor1,

Y.J. Park1, D.D. Keiser, Jr.*2,

Y.H. Sohn1, 1University of

Central Florida, USA, 2Idaho


[O3.12]

Grand potential modeling

of nanoscale zirconium

hydride precipitates in a

zirconium matrix

P-C. Simon*1, A.T. Motta1,

M.R. Tonks2, 1The

Pennsylvania State

University, USA, 2University of

Florida, USA

[O5.12]

Thermophysical properties,

microstructure, and

oxidation behavior of UN-

UO2 composites

N.R. Wozniak*1, J.T. White1,

A.T. Nelson1 ,2, 1Los Alamos


2Oak Ridge National

Laboratory, USA

12:00-

12:35

[T8.INV02]

In situ Raman

spectroscopy on

nuclear materials in

hot cell

S. Miro*1, S.

Peuget1, M. Tupin2,

L. Fayette3, A.

Nakayoshi4, C.

Jégou1, 1CEA, DEN,

DE2D, France,

2CEA, DEN, DMN,

France, 3CEA, DEN,

DEC, France,

4Atomic energy

Agency (JAEA),

France

12:25-13:25 Lunch Break | Room: Emerald



Fission and Fusion

reactors

Room: Seattle 1 Session Chair: M. Sokolov



Materials

Room: Seattle 2



Track 7- Characterization of

Irradiated Materials and

Nuclear Fuels

Room: Seattle 3

Session Chairs: K. Field,

A. Leenaers

Track 6- Radiation Damage

Processes in Materials and

Complex Microstructures

Room: Belltown

Session Chairs: M. Lang,

L. Walters, K. Arakawa




Tolerant Fuels

Room: Pioneer

Session Chair: M. Steinbrück

Track 1- Thermodynamics

and Thermal Properties of

Nuclear Fuels Room: Capitol Hill

Session Chair:

T.M. Besmann

13:25-13:50 [O2.14]

Microstructure evolution

and radiation hardening

of proton-irradiated

reactor pressure vessel

steels

H-H. Jin*1, E. Ko1 ,2, S.

Lim1, M-C. Kim1, J.

Kwon1, G-G.

[O4.12]

The formation and structure

of Fe-Mn-Ni-Si solute

clusters and G-phase

precipitates in steels

D.J.M. King*1, P.A. Burr2, S.C.

Middleburgh3 ,5, T.M.

Whiting1, M.G. Burke4, M.R.

Wenman1, 1Imperial

[O7.14]

Determining enrichment

and distribution of

uranium isotopes in

metallic nuclear fuel with

atom probe tomography

E. Kautz*, A. Devaraj, V.

Joshi, D. Burkes, C.

Lavender, Pacific

[O6.01]

Atomic-scale observation

of antisite defects and the

formation of solid solutions

in Mn+1AXn phases

C. Wang*1 ,2, T. Yang2, C.L.

Tracy1, 1Stanford University,

USA, 2Peking University,

China, 3University of

[O5.13]

Analytical development

of oxidation models for new

perspective types of

accident tolerant fuel

claddings

A.D. Vasiliev, Nuclear

Safety Institute, Russia

[O1.01]

Low temperature thermal

conductivity of ThxU1-xO2

oxides

J-C. Griveau*, O. Valu, K.

Popa, European

Commission, Germany


Lee1, 1Korea Atomic

Energy Research

Institute, Republic of

Korea, 2KEPCO,

Republic of Korea

College London, UK,

2University of New South

Wales, Australia,


Sweden, Sweden, 4The

University of Manchester,

UK, 5Bangor University, UK

Northwest National

Laboratory, USA

Michigan, USA, 4Monash

University, Australia,

5Chinese Academy of

Sciences, China



Fission and Fusion

reactors




Materials

Room: Seattle 2

Session Chair: B. Wirth, T.

Okita, M. Gilbert



Nuclear Fuels

Room: Seattle 3

Session Chair: K. Field, A.

Leenaers




Room: Belltown

Session Chair: M. Lang, L.

Walters, K. Arakawa




Tolerant Fuels

Room: Pioneer

Session Chair: M. Steinbrück




Session Chair: T.M. Besmann

13:50-14:15 [O2.15]

Investigation of

susceptibility of A533B

steel to temper

embrittlement

M.A. Sokolov*1, B.A.

Gurovich2, E.A.

Kuleshova2, Z.V. Bukina2,

A.S. Frolov2, D.A.

Maltsev2, S.V.

Fedotova1, 1Oak Ridge


USA, 2NRC “Kurchatov

Institute”, Russia

[O4.13]

Density functional theory

simulations of solute triplets

in reactor pressure vessel

steels

T.M. Whiting*1, D.J.M. King1,

P.A. Burr2, M.R.

Wenman1, 1Imperial

College London, UK,

2University of New South

Wales, Australia

[O7.15]

Investigation of grain

boundary segregation by a

correlative EBSD/TKD/APT

methodology for a 16MND5

weld metal

L. Zhang1, B. Radiguet1, C.

Domain2, Y. Shen3, P.

Todeschini2, P.

Pareige*1, 1Normandie

University, France, 2EDF Lab,

France, 3EDF DIPNN, France

[O6.02]

Effects of electronic energy

loss on the production and

evolution of radiation

damage in nuclear

ceramics

W.J. Weber*1 ,2, E.

Zarkadoula2, Y.

Zhang2, 1University of

Tennessee, USA, 2Oak Ridge


[O5.14]

Fabrication,

characterisation and testing

of Cr coated Zr alloy

cladding for enhanced

accident tolerance

D.T. Goddard1, A. Evans*2,

P. Kelly2, G. Obasi3, M.

Preuss3, A. Cole-Baker4, E.P.

Vernon1, 1National Nuclear

Laboratory, UK, 2Manchester

Metropolitan University, UK,

3University of Manchester,

UK, 4Wood plc, UK

[O1.02]

Effect of off-stoichiometry and

grain size on thermal

transport in uranium dioxide

K. Gofryk,

Idaho National Laboratory,

USA

14:15-14:40

[O2.16]

Correlation between

master curve testing and

Charpy impact test

results of long term

thermally aged VVER-

440 RPV surveillance

specimens

M. Kolluri*1, H. Nolles1,

F.J. Frith1, Z. Szaraz2, O.

Martin2, P. Hähner2, V.

Petrosyan3, A.

Petrosyan3, G.

Sevikyan4, 1Nuclear

Research & consultancy

Group (NRG), The

Netherlands, 2European

Commission, The

Netherlands,

3ARMATOM, Armenia,

4ANPP, Armenia

[O4.14]

Entropy contributions to

phase stability in binary

random solid solutions

A. Manzoor*1, S.

Pandey2, D.

Chakraborty1, S.

Phillpot2, D.

Aidhy1, 1University of

Wyoming, USA,

2University of Florida, USA

[O7.16]

Post-irradiation examination

of metallic components

from tritium producing

burnable absorber rods

using atomic-scale

scanning transmission

electron microscopy

E.C. Buck*, P.J. MacFarlan,

D.D. Reilly, G.J.

Sevigny, Pacific Northwest


[O6.03]

Radiation-induced volume

swelling and microcracking

in glass ceramic and

crystalline ceramic nuclear

waste forms

M. Tang

Los Alamos National

Laboratory, USA

[O5.15]

Experimental Behavior of

Chromium Based Coatings

for Nuclear Reactor Fuel

J. Krejci*1 ,2, M. Sevecek2, L.

Cvrcek3, P. Sutta4, P.

Bublikova5, J. Kabatova1, J.

Malek1 ,3, S. Krum3, P.

Halodova5, H.K.

Namburi5, 1UJP PRAHA a.s.,

Czech Republic, 2CTU in

Prague, Faculty of Nuclear

Sciences and Physical

Engineering, Czech

Republic, 3CTU in Prague,

Faculty of Mechanical

Engineering, Czech

Republic, 4University of West

Bohemia, New Technologies

– Research Centre, Czech

Republic, 5Research Centre

Řež, Czech Republic

[O1.03]

Experimental and

computational determination

of U-Si-N phase behavior for

application in advanced

fuels

D.A. Lopes*1, T.L. Wilson1, V.

Kocevski1, T.M. Besmann1, J.T.

White2, A. Claisse3, 1University

of South Carolina, USA, 2Los

Alamos National Laboratory,

USA, 3Westinghouse Electric

Co, Sweden




Fission and Fusion

reactors




Materials

Room: Seattle 2





Nuclear Fuels

Room: Seattle 3


A. Leenaers




Room: Belltown






Tolerant Fuels

Room: Pioneer

Session Chair: A. Evans




Session Chair:

T.M. Besmann

14:40-15:15 [T2.INV02]

Insights into the

mechanisms of

irradiation assisted stress

corrosion cracking G.S. Was*1, D. Johnson1, M-R. He2, I. Robertson2, 1University of Michigan, USA, 2University of Wisconsin, USA

[T4.INV02] Prediction of nuclear materials behavior for reactors life-span extension: Towards a multi-scale approach dedicated to microstructure and mechanical properties of irradiated materials C. Gallé*, L. Dupuy, T. Jourdan, L. Gélébart, CEA, France

[T7.INV02]

Nanoscale

characterization of

novel fuel claddings

using complementary

SANS-APT-STEM

techniques

K.G. Field*1, D. Zhang1,

S.A. Briggs2, C.P.

Massey3, K.C.

Littrell1, 1Oak Ridge


USA, 2Sandia National

Laboratories, USA,

3University of Tennessee,

USA

[T6.INV01]

Radiation damage in

oxide systems for nuclear

materials: A short review

G.R. Lumpkin*, R.D.

Aughterson, M. de los

Reyes, M.J. Qin, S.C.

Middleburgh, Z.

Zhang, Australian Nuclear

Science and Technology

Organisation, Australia

[T5.INV03]

Framatome's enhanced


developments: Focus on

chromium-coated claddings

N. Chaari*1, J. Bischoff1, P.

Barberis1, C. Delafoy1, F.

Bourlier1, K.

Nimishakavi2, 1Framatome,

France, 2Framatome Inc., USA

[T1.INV01]

Thermochemistry of the

uranium silicide system

A.T. Nelson*1, J.W. White2,

E.S. Wood3, 1Oak Ridge


2Los Alamos National

Laboratory, USA, 3University

of Texas at San Antonio,

USA

15:15-15:45 Coffee Break | Room: Emerald



Fission and Fusion

reactors

Room: Seattle 1 Session Chair:

M. Sokolov



Materials

Room: Seattle 2





Nuclear Fuels

Room: Seattle 3


A. Leenaers




Room: Belltown






Tolerant Fuels

Room: Pioneer





Session Chair:

T.M. Besmann

15:45-16:10 [O2.17]

Microstructural

evolution in proton-

irradiated A508 Gr4N

forging steel

A. Carruthers1, M.G.

Burke*1, J. Hyde2, S.

Dumbill2, 1University of

Manchester, UK,

2National Nuclear

Laboratory, UK

[O4.15]

A new insight into void

swelling near grain

boundary from phase-

field simulations

Y.Y. Wang*1, J.H. Ding1,

J.J. Zhao1, Y.Z.

Wang2, 1Dalian University

of Technology, China,

2The Ohio State University,

USA

[O7.17]

Real-time property

monitoring during ion beam

irradiation using transient

grating spectroscopy

C.A. Dennett*1, K. Hattar2,

M.P. Short1, 1Massachusetts

Institute of Technology, USA,

2Sandia National

Laboratories, USA

[O6.04]

Simulations show how

lattice strain evolution in

irradiated materials is

driven by changes in

defect configuration

J-P. Crocombette*1,

A. Debelle2 ,1, A.

Boulle3, A.

Chartier1, 1Universit

é Paris-Saclay,

France, 2Université

Paris-Sud, France,

3SPCTS, France

[O5.16]

Chromium hardening and

Zr-Cr interface stability of

irradiated chromium-

coated Zircaloy-4 alloy

J. Ribis*1, A. Wu1, J.C.

Brachet1, E. Clouet1, B.

Arnal1, E. Rouesne1, S.

Urvoy1, F. Barcelo1, A.

Gentils2, C. Baumier2, 1CEA,

France, 2Université Paris Sud,

France, 3Framatome,

France, 4EDF, France

[O1.04]

Evidence of the negative

thermal expansion of the

UO2.00 fluorite local structure

P.M. Martin*1, D. Prieur2 ,3, E.

Epifano1, K. Dardenne4, J.

Rothe4, C. Hennig2 ,3, A.C.

Scheinost2 ,3, D.

Neuville5, 1CEA Marcoule,

France, 2Helmholtz-Zentrum

Dresden-Rossendorf,

Germany, 3European

Synchrotron Radiation

Facility, France, 4Karlsruhe


Germany, 5Institut de


Physique du Globe de Paris-

CNRS, France



Fission and Fusion

reactors

Room: Seattle 1

Session Chair: M. Sokolov



Materials

Room: Seattle 2





Nuclear Fuels

Room: Seattle 3


A. Leenaers




Room: Belltown






Tolerant Fuels

Room: Pioneer





Session Chair:

T.M. Besmann

16:10-16:35 [O2.18]

Positron annihilation spectroscopy studies on ferritic/martensitic steels exposed to different radiation environments

V. Krsjak*1, Y. Dai2, J.

Degmova1, V.

Slugen1, 1Slovak

University of Technology,

Slovakia, 2Paul Scherrer

Institut, Switzerland

[O4.16]

Modeling of hardening in spinodally-decomposed Fe-Cr binary alloys

T. Suzudo*1, H. Takamizawa1,

Y. Nishiyama1, A. Caro2, T.

Toyama3, Y. Nagai3, 1Japan


Japan, 2George Washington

University, USA, 3Tohoku

University, Japan

[O7.18]

Fracture properties

characterization of nuclear

fuel using micro-cantilever

bending

R. Henry*1, T. Blay2, I.

Zacharie-Aubrun2, J-M.

Gatt2, C. Langlois1, S.

Meille1, 1INSA-Lyon, France,

2CEA Cadarache, France

[O6.05]

Atomistic modeling of

defects and diffusion in

tritium-producing burnable

absorber rod pellets

W. Setyawan, G.

Nandipati, D.J. Senor, R.

Devanathan*, Pacific

Northwest National

Laboratory, USA

[O5.17]

Development of cold

spray coatings for


cladding

B.R. Maier*1, H. Yeom1,

G.O. Johnson1, T.

Dabney1, J. Walters2, H.

Shah2, J. Romero2, K.

Sridharan1, 1University of



Company, USA

[O1.05]

Modelling the Nuclear Fuel

- Cladding interaction and

Fission Products behaviour

during a simulated Severe

Accident (VERDON-1 test)

with the TAF-ID

E. Geiger*1, Y. Pontillon2, M.

Piro1, C. Guéneau3, E.

Corcoran4, 1University of

Ontario Institute of

Technology, Canada,

2Commissariat à l’Energie

Atomique et aux Energies

Alternatives, France,

3Université Paris-Saclay,

France, 4Royal Military

College of Canada,

Canada

16:35-17:00 [O2.19]

Microstructural and

micromechanical

characterization of

laser weld repairs on

neutron irradiated 304

stainless steel

K. Mao*1 ,2, L.A.

Giannuzzi3, P.D. Freyer4,

C. Sun1 ,2, J.P. Wharry1,

F.A. Garner5, 1Purdue

University, USA, 2Idaho


USA, 3L.A. Giannuzzi &

Associates LLC, USA,


Company LLC, USA,


USA

[O4.17]

Phase-field model simulation

of spinodal decomposition in

Fe-Cr-X ternary alloys

G. Obulan Subramanian*, B.

Kong, C. Jang, Korea

Advanced Institute of

Science and Technology,

Republic of Korea

[O7.19]

Advanced EBSD-and STEM-

based methodologies for

studying nuclear materials

C.M. Parish*1, K. Wang1, A.

Bhattacharya1, P.D.

Edmondson1, R. Doerner2,

M. Baldwin2, Y.

Katoh1, 1Oak Ridge


2University of California San

Diego, USA

16:35-

17:10 [T6.INV02]

Deformation

mechanisms in

zirconium alloys

under and after

irradiation

F. Onimus*1, M.

Gaumé1, F.

Mompiou2, L.

Dupuy1, W.

Kassem1, L.

Gélébart1, R.

Brenner3, 1Universi

té Paris-Saclay,

France, 2Centre

d'Elaboration de

Matériaux et

d'Etudes

Structurales,

[O5.18]

Fatigue behavior of cold

spray-coated accident

tolerant cladding

M. Sevecek*1 ,2, M. Shahin2,

J. Petrik2, R. Ballinger2, K.

Shirvan2, 1Czech Technical

University in Prague, Czech

Republic, 2Massachusetts

Institute of Technology, USA

[O1.06]

Validation of TAF-ID

thermodynamic database

based on post irradiation

examinations of high

burnup MOX fuel in fast

reactors

K. Samuelsson*1, J-C.

Dumas2, B. Sundman3, C.

Guéneau2, 1KTH Royal


Sweden, 2CEA, France,

3INSTN, France


France, 3Sorbonne

Université, France

17:00-18:45 Poster Session 2 (Refreshments will be available to purchase) | Room: Emerald

Wednesday 17th October 2018 08:30-09:10 [PS05] Room: Seattle 1-3

The role of compositional complexity on irradiation effects in concentrated solid solution alloys

Y. Zhang, Oak Ridge National Laboratory, USA

09:10-09:50 [PS06]

Materials challenges for future nuclear fuel cycles – R&D on nitride fuel cycle for MA transmutation

M. Takano, Japan Atomic Energy Agency, Japan




Fission and Fusion

reactors

Room: Seattle 1

Session Chair: G. Was



Materials

Room: Seattle 2





Nuclear Fuels

Room: Seattle 3

Session Chairs: M. Preuss,

T. Wiss




Room: Belltown

Session Chair: W. Weber



Room: Pioneer

Session Chair: C. Valot

Track 1 Continued

Room: Capitol Hill

Session Chair: E.C.

Corcoran

10:20-10:45 [O2.20]

Helium effects in

materials of the nuclear

importance

S. Agarwal*, J. Brechtl,

S.J. Zinkle, University of

Tennesseee, USA

[O4.18]

Quantum mechanical simulations of displacement cascades in metals

P. Olsson*, D. Karlsson, KTH Royal Institute of Technology, Sweden

[O7.20]

Effect of thermal and

irradiation-induced long

range ordering in Ni-Cr

model alloys

F. Teng*1, D. Sprouster2, H.T.

Vo3, L.J. Yu4, E. Marquis4, P.

Hosemann3, J.

Tucker1, 1Oregon State

University, USA, 2Brookhaven


3University of California

Berkeley, USA, 4University of

Michigan, USA

[O6.06]

Nano-scale microstructure

damage by neutron

irradiations in a novel Boron-

11 enriched TiB2 ultra-high

temperature ceramic

A. Bhattacharya*1, T.

Koyanagi1, C. Parish1, C.

Ang3, D. King2, G. Hilmas2, W.

Fahrenholtz2, S. Zinkle1 ,3, Y.

Katoh1, 1Oak Ridge National

Laboratory, USA, 2Missouri

University of Science and

Technology, USA, 3University

of Tennessee, USA

[O3.13]

Stability of uranium

vacancies, oxygen

interstitial clusters and U4O9

phase in hyper-

stoichiometric UO2 with DFT-

empirical free energies

calculations and empirical

molecular dynamics

simulations

A. Soulié*1, F. Bruneval1, M-

C. Marinica1, S. Murphy2, F.

Garrido3, J-P.

Crocombette1, 1CEA DEN

Service de Recherche en

Métallurgie Physique,

France, 2Lancaster

University, UK, 3Université

Paris-Sud, France

[O1.07]

First-principles studies of

mechanical, vibrational,

thermodynamic and thermal

transport properties of UAlx

(x=2,3,4)

Z.G. Mei*1, A.M. Yacout1, J.

Yang2, 1Argonne National

Lab, USA, 2Shanghai

University, China

10:45-11:10 [O2.21]

Grain boundary

embrittlement of neutron

irradiated Inconel X-750

M. Griffiths*1, S.

Xu2, 1Queens University,

Canada, 2Kinectrics Inc,

Canada

[O4.19]

Understanding of nano size

<100> interstitial loop within

high displacement

cascades and their

migration in iron-based

alloys

F. Gao*1, Q. Peng1, N. Gao2,

R.J. Kurtz3, 1University of

Michigan, USA, 2Chinese

[O7.21]

Microstructural

characterization of

neutron-irradiated

polycrystalline TiC.

S. Agarwal*1, T.

Koyanagi2, Y. Katoh2 ,1, X.

Hu1, W.J. Weber1 ,2, S.J.

Zinkle1 ,2, 1University of

Tennesseee, USA, 2Oak

[O6.07]

The swelling equation: From

10-2 to 10-8 dpa/s

M.J. Fluss, U.C. Berkeley, USA

[O3.14]

A DFT study of burnup-

induced volume changes in

U3Si2

A. Claisse*1, S.

Middleburgh2, D.

Nanopoulos3, P.

Olsson3, 1Westinghouse

Electric Sweden, Sweden,

2Bangor University, UK, 3KTH

[O1.08]

Assessment of Sb and Te as

U-Zr fuel additive to mitigate

fuel-cladding chemical

interaction

J. Zhang*1, Y. Xie1, M.

Benson2, R.D. Mariani1 1Virginia Tech, USA, 2Idaho



Academy of Sciences,

China, 3Pacific Northwest


Ridge National

Laboratory, USA

Royal Institute of

Technology, Sweden

Track 2 Continued

Room: Seattle 1

Session Chair: G. Was



Materials

Room: Seattle 2





Nuclear Fuels

Room: Seattle 3

Session Chairs: M. Preuss,

T. Wiss




Room: Belltown

Session Chair: W. Weber



Room: Pioneer


Track 1 Continued

Room: Capitol Hill

Session Chair:

E.C. Corcoran

11:10-11:35 [O2.22]

Understanding the grain

boundary strength of X-

750 alloy by small scale

tensile testing and

advanced

characterization and

modeling

L. He*1, M. Bachhav1, D.

Murray1, X. Liu1, E. Perez1,

W. Jiang1, X. Bai2, C.

Sun1, S.

Teysseyre1, 1Idaho


USA, 2Virginia

Polytechnic Institute and


[O4.20]

The effects of applied strain

on defect formation process

under high energy of a

primary knock-on atoms in

face-centered cubic metals

K. Kawamitsu1, T. Okita*1, T.

Kawabata1, M. Itakura2, 1The

University of Tokyo, Japan,


Agency, Japan

[O7.22]

Radiation damage with a

twist - a study of helical

dislocations in irradiated

FeCr alloys

J.C. Haley*1, G.R. Odette2,

S. Lozano-Perez1, S.G.

Roberts1, 1University of

Oxford, UK, 2University of

California Santa Barbara,

USA

[O6.08]

Descriptions of energy

deposition rates of self-ions

and their impact on the

credibility of simulation of

neutron-induced swelling

F.A. Garner*1 ,2, L.

Shao1, 1Radiation Effects

Consulting, USA, 2Texas

A&M University, USA

[O3.15]

Fission gas behaviour in

U3Si2 from DFT calculations

and atomistic simulations

D.A. Andersson*, X-Y. Liu,

M.W.D. Cooper, Los Alamos


[O1.09]

Vapor pressure

measurement of cesium

and iodine dissolved in

molten LiF-NaF-KF Salt by

TG-DTA-MS

Y. Sekiguchi*1, T. Kato2, K.

Uozumi2, T. Terai1, 1The

University of Tokyo, Japan,

2Central Research Institute

of Electric Power Industry,

Japan

11:35-12:00 [O2.23]

Quantitative

determination of the

stress state required to

induce crack initiation in

irradiated austenitic

stainless steels

D.C. Johnson*, G.S.

Was, University of

Michigan, USA

[O4.21]

Threshold displacement

energy of bcc metals by

molecular dynamics

simulation using force-

matching potential

S. Park*, T. Oda, Seoul

National University, Republic

of Korea

[O7.23]

Study on degree of

recrystallization in

zirconium-niobium cladding

using image quality by EBSD

T.S. Jung*, H. Jang, Y.K. Mok,

J.I. Kim, J.S. Yoo, KEPCO NF,

Republic of Korea

[O6.09]

Use of pure iron to study

the impact of self-ion

energy, displacement per

atom value, displacement

rate and irradiation

temperature on charged

particle simulation of void

swelling: swelling in four

dimensions

A.J. French*, F.A. Garner, L.

Shao, Texas A&M

University, USA

[O3.16]

Monte-Carlo and

molecular dynamics study

of PuO2 and UO2 properties

by use of improved

charge-variable SMTBQ

interatomic potentials

R. Ducher*1, D. MBongo1, A.

Shahsavari1, R. Tétot2, R.

Dubourg1, 1Institut de

Radioprotection et de

Sûreté Nucléaire, France,

2Institut de Chimie

Moléculaire et des

Matériaux d'Orsay, France

[O1.10]

Noble metal fission products

behaviour in Molten Salt

Reactor

E. Capelli*1 ,2, F. Cappia3,

P.R. Hania2, R.J.M.

Konings1,4, 1Delft University

of Technology, The

Netherlands, 2NRG, The

Netherlands, 3Idaho



Germany

12:00-12:25 [O2.24]

Experiments and

simulations with In-situ

Depth markers for

Evaluating high-z

[O4.22]

The evolution processes of

self-interstitial atom clusters

under displacement

cascades in FCC metals

[O7.24]

Development of methods for

post-irradiation examination

of miniature fuel specimens

irradiated in the High Flux

[O6.10]

Defect-free zones in

irradiated materials

S.J. Zinkle1 ,2, 1University of


[O3.17]

Modeling and assessment

of intra-granular bubble

evolution and coarsening

in uranium dioxide

[O1.11]

Thermodynamic modeling

and database development

for molten salt reactor fuel

performance simulation


materials with AIMS

(iDEA)

L.A. Kesler*, K.B. Woller,

Z.S. Hartwig, D.G.

Whyte, Massachusetts


USA

S. Hayakawa*1, T. Okita1, M.

Itakura2, H. Xu3, Y.N.

Osetsky4, 1The University of

Tokyo, Japan, 2Japan


Japan, 3The University of



Isotope Reactor

A. Raftery*, C. Petrie, R.

Morris, K. Smith, S. Finkeldei,

K. Terrani, Oak Ridge


National Laboratory, USA T. Barani*1, A. Magni1, D.

Pizzocri1, L. Cognini1, P. Van

Uffelen2, L. Luzzi1, G.

Pastore3 ,4, 1Politecnico di

Milano, Italy, 2European

Commission, Joint Research

Centre, Directorate for

Nuclear Safety and

Security, Germany, 3Idaho


4Massachusetts Institute of

Technology, USA

T.M. Besmann*1, J.C. Ard1,

J.W. McMurray2, D.

Shin2, 1University of South

Carolina, USA, 2Oak Ridge


12:25-13:25

13:25-16:10

Lunch Break | Room: Emerald



Fission and Fusion

reactors

Room: Seattle 1


T.S. Byun



Materials

Room: Seattle 2





Nuclear Fuels

Room: Seattle 3

Session Chairs: C. Judge,

A. Leenaers




Room: Belltown

Session Chair: G. Lumpkin



Room: Pioneer


Track 1 Continued

Room: Capitol Hill

Session Chairs: C.A Atkins,

E.C. Corcoran

13:25-13:50 [O2.25]

Phase stability of a 14Cr-

ODS ferritic steel

strengthened by Y-Ti-O

oxide particles under Fe

ions irradiation at room

temperature

P. Song*, A. Kimura, K.

Yabuuchi, Kyoto

University, Japan

[O4.23]

The effect of local chemical

environment on the

energetics of stacking faults

and vacancy platelets in

zirconium

J. March-Rico*, B.D. Wirth, G.

Huang, University of

Tennessee, USA

[O7.25]

The MARS beamline, a

unique multipurpose

instrument for the

examination of

radioactive samples with

advanced synchrotron

techniques

D. Menut*, M.O.J.Y.

Hunault, H. Hermange,

P.L. Solari, Synchrotron

SOLEIL, France

[O6.11]

Atomic scale instrumental

methodology to quantify

intergranular segregation:

Application to phosphorous

in ferritic thermally aged or

irradiated alloys

A. Akhatova1, F. Christien2,

V. Barnier2, E. Cadel1, F.

Cuvilly1, B. Radiguet1, P.

Pareige*1, 1Normandie

University, France, 2Ecole

des Mines Sait Etienne,

France

[O3.18]

Temperature dependence

of phonon spectra of UMo

alloys with 12.5 and 25 at.%

Mo

B. Dorado*1, D. Chaney2, J.

Bouchet1, G.H.

Lander3, 1CEA, France,

2University of Bristol, UK, 3JRC,

Germany

[O1.12]

Applicability of Machine

Learning to Modeling Thermal

Conductivity of Irradiated

Uranium-Molybdenum

Nuclear Fuels

E. Kautz*, J. Johns, A. Hagen,

D. Burkes, Pacific Northwest


13:50-14:15 [O2.26]

Fabrication and

characterization of thin-

walled ODS FeCrAlY tubes

for accident tolerant fuel

cladding applications

S. Dryepondt*1, C.P.

Massey2, M.N. Gussev1,

K.D. Linton1, K.A.

Terrani1, 1Oak Ridge


United States Minor

Outlying Islands, 2University

of Tennessee, United

States Minor Outlying

Islands

[O4.24]

Fast efficient modelling of

hydrided microstructures of

zirconium at the millimetre

scale

P. Patel, D.S. Balint, A.P.

Sutton,

M.R. Wenman*, Imperial

College London, UK

[O7.26]

Advanced characterisation

of iodine-induced stress

corrosion cracks in

zirconium alloys

A. Garner*, C. Gillen, P.

Frankel, University of

Manchester, UK

[O6.12]

Atom-probe

tomography

characterization of

nano-sized hardening

features of high-dose

neutron irradiated

Eurofer97

B. Gómez-Ferrer*1, C.

Dethloff2, E. Gaganidze2,

L. Malerba3, P. Pareige1,

C. Pareige1, 1Universite

de Rouen - CNRS,

France, 2Karlsruhe


Germany, 3SCK•CEN,

[O3.19]

Microstructure dependent

swelling model in monolithic

UMo nuclear fuels by

coupling the rate theory and

phase field approach

S.Y. Hu*, V.V. Joshi, C.A.

Lavender, D.E. Burkes, Pacific

Northwest National

Laboratory, USA

[O1.13]

Development of effective

thermal conductivity model

for FCM and pebble fuels with

randomly distributed TRISO

particles

M. Liu1, Y. Lee*1, D.V.

Rao2, 1University of New

Mexico, USA, 2Los Alamos



Belgium



Fission and Fusion

reactors

Room: Seattle 1


T.S. Byun



Materials

Room: Seattle 2





Nuclear Fuels

Room: Seattle 3


A. Leenaers




Room: Belltown




Room: Pioneer

Session Chair:

G. Pastore

Track 1 Continued

Room: Capitol Hill


E.C. Corcoran

14:15-14:40 [O2.27]

Evolution of materials

properties and

macropores in thermally

crept nuclear graphite

J.J. Kane*, T.S. Yoder,

W.E. Windes, Idaho


USA

[O4.25]

DFT studies on the nature

of Y-Ti-O nanoclusters in

bcc Fe

M. Vallinayagam*, M.

Posselt, J.

Faßbender, Institute of

Ion Beam Physics and

Materials Research,

Germany

[O7.27]

Digital image correlation

strain measurement and

geometrically necessary

dislocation determination at

a crack tip in zirconium

Z. Wang*, M.

Daymond, Queen's

University, Canada

[O6.13]

In situ Raman spectroscopy

for characterization of ion

induced defects in model

graphite

N. Galy1, N. Moncoffre*1, N.

Toulhoat1 ,2, N. Bérerd1 ,3, Y.

Pipon1 ,3, M.R. Ammar4, P.

Simon4, A. Canizarès4, N.

Raimboux4, P.

Sigot4, 1Université de lyon,

France, 2CEA Saclay,

France, 3UCBL IUT A, France,

4CNRS CEMHTI, France

[O3.20]

The role of dopant charge

state on defect chemistry

and grain growth of

doped UO2

M.W.D. Cooper*, C.R.

Stanek, D.A.

Andersson, Los Alamos


[O1.14]

Viscosities of stainless steel

and boron-carbide alloy

melts

T. Nishi*1, H. Ohta1, H.

Kokubo1, H.

Yamano2, 1Ibaraki University,

Japan, 2Japan Atomic

Energy Agency, Japan

14:40-15:15 [T2.INV03] Phase stability of oxide

particles under ion-irradiation in different sorts of ODS ferritic steels

A. Kimura*, P. Song, K. Yabuuchi, Kyoto University, Japan

[T4.INV03] Using computational modeling to understand radiation damage tolerance in complex oxides both from the bottom-up and the top -down B.P. Uberuaga, Los Alamos National Laboratory, USA

[T7.INV03] Image analysis and computer vision: A tool for investigating irradiated fuel microstructure F. Cappia*, G.L. Beausoleil, L. Capriotti, G.L. Povirk, J.M. Harp, Idaho National Laboratory, USA

[T6.INV03]

Radiation damage in

irradiated thermal and fast

nuclear reactor fuels

T. Wiss*1, O. Dieste1, R.

Konings1, V. Rondinella1, D.

Staicu1, O. Benes1, D.

Wegen1, N.

Chauvin2, 1European

Commission, Germany,

2Centre d’études

nucléaires de Cadarache,

France

[T3.INV03]

Combining CALPHAD,

phase-field, and

transport models for

quantitative prediction

of nuclear materials

behaviour

M.J. Welland*, A.A.

Prudil, E. Thomas, E.

Tenuta, Canadian


Canada

[T1.INV02]

Determination of

melting transitions in

fast reactor fuels

K. Ananthasivan*1 ,2, B.

Samanta1 ,2, S.

Balakrishnan1, K.

Joseph1, 1Indira

Gandhi Centre for

Atomic Research,

India, 2Homi Bhabha

National Institute, India



15:45-16:10 [O2.28]

Preparing highly

structured B4C control-

rod via magnetic field-

assisted colloidal

processing

S. Azuma*1, T. Uchikoshi1,

K. Yoshida2, T.S.

Suzuki1, 1National

Institute for Materials

Science, Japan, 2Tokyo


Japan

[O4.26]

The effect of nanoscale

precipitates on the

mechanical properties of

T91 steel during early aging

based on experimental and

computational analysis

L.J. Hu*, Q.F. Zhang, H.Y.

Dong, W.Y. Liang, B.Q. Lin,

M.Y. Yao, Y.P. Xie, Shanghai

University, China

[O7.28]

Characterizing swift heavy

ion induced effects in

nuclear materials with

neutron total scattering

M. Lang*1, E.C. O'Quinn1,

R.I. Palomares1, I. Gussev1,

J. Neuefeind2, C.

Trautmann3 ,4, R.C.

Ewing5, 1University of

Tennessee, USA, 2Oak

Ridge National Laboratory,

USA, 3GSI Helmholtzzentrum

für Schwerionenforschung,

Germany, 4Technische

Universität, Germany,

5Stanford University, USA

[O6.14]

Developing a method to

quantify radiation damage

using stored energy

C.A. Hirst*, R.C. Connick, K.

So, P. Cao, R.S. Kemp, M.P.

Short, Massachusetts


USA

[O3.21]

Development of the MFPR/R

code for characterization of

the rim zone and high

burnup structure evolution in

UO2 fuel pellets

V.I. Tarasov1, V.E. Shestak1,

P.V. Polovnikov1, M.S.

Veshchunov*2, 1Russian

Academy of Sciences,

Russia, 2International Atomic

Energy Agency (IAEA),

Austria

[O1.15]

Phase identification and

thermophysical properties

of Pu-Zr and U-Pu-Zr fuel

alloys

C. Adkins*1, A. Aitkaliyeva2

,1, S. Middlemas1, 1Idaho


2University of Florida, USA



Fission and Fusion

reactors

Room: Seattle 1


T.S. Byun



Materials

Room: Seattle 2





Nuclear Fuels

Room: Seattle 3


A. Leenaers




Room: Belltown




Room: Pioneer


Track 1 Continued

Room: Capitol Hill


E.C. Corcoran

16:10-16:35 [O2.29]

Irradiation induced

hydrothermal corrosion

of SiC and the

surface passivation for

ATF

S. Kondo, Tohoku

University, Japan

[O4.27]

Radiation damage tolerant

materials: Zr-Nb nanoscale

metallic multilayer composite

H.S. Sen*, T. Polcar, Czech

Technical University in

Prague, Czech Republic

[O7.29]

Neutron irradiation effects on

the microstructure of nuclear

graphite

J.D. Arregui-Mena*1, B.

Maerz2, C. Contescu1, H.

Wu2, A.A. Campbell1, R.N.

Worth3, P.D. Edmondson1,

J.W. Geringer1, Y.

Katoh1, 1Oak Ridge National

Laboratory, USA,

2Loughborough University,

UK, 3The University of

Manchester, UK

[O6.15]

Theoretical prediction of

void superlattice formation

under irradiation

Y. Zhang*1, Y. Gao1, C. Sun1,

D. Schwen1, C. Jiang1, L.

He1, J. Gan1, D. Sprouster2,

L. Ecker1, 1Idaho National

Laboratory, USA,

2Brookhaven National

Laboratory, USA

[O3.22]

Molecular dynamics

modeling of grain boundary

mobilities in UO2

J. French, X.M. Bai*, Virginia

Polytechnic Institute and


[O1.16]

Annealing effects on

thermal diffusivity and

electrical resistivity of a

surrogate for metallic fuel

N. Odaira*, Y.

Arita, University of Fukui,

Japan

16:35-17:00 [O2.30]

Analysis of irradiation

induced element

redistribution in TPBAR

components using atom

probe tomography

[O7.30]

Mechanisms of

embrittlement and fracture

for Inconel X-750 irradiated

to high dose and high

concentrations of helium

[O6.16]

Combined study of

microstructure evolution of

irradiated and deuterium

exposed Eurofer and

tungsten

[O3.23]

Development of a

molecular dynamics

methodology to examine

the dynamic structure of

vacancies in nuclear fuel

[O1.17]

Fuel fabrication and

characterization of

surrogate fuel blocks for the

low-enriched fuel

conversion effort at the


A. Devaraj, B. Arey, E.J.

Kautz*, G. sevigny, J.

Hardy, D. Senor, Pacific

Northwest National

Laboratory, USA

and hydrogen

C.D. Judge*, V. Bhakhry, C.

Howard, C. Mayhew, C.

Dixon, H. Rajakumar, G.A.

Bickel, Canadian Nuclear

Laboratories, Canada

A. Hollingsworth*1, A. Baron-

Wiechec1, A. Davies1, M.F.

Barthe3, 1Culham Science

Centre, UK, 2University Paris-

Saclay, France, 3Université

d'Orléans, France

C.A. Manring*, A.I.

Hawari, North Carolina


Transient Reactor Test

Facility

E. Luther*1, B. Coryell2, S.

Kwon2, J. Jiang2, D. Scates2,

J. Aguiar2, D. Cummins1, T.

Baker1, H. Hartman2, 1Los

Alamos National

Laboratory, USA, 2Idaho


17:00-18:45 Poster Session 3 (Refreshments will be available to purchase) | Room: Emerald

Thursday 18th October 2018 08:30-10:10 Track 2- Structural and


Fission and Fusion

reactors

Room: Seattle 1

Session Chair: S.S. Raiman



Materials

Room: Seattle 2





Nuclear Fuels

Room: Seattle 3

Session Chairs: T. Lach,

J. Wharry




Room: Belltown






Tolerant Fuels

Room: Pioneer

Session Chair: M.K. Grosse


Simulation of Nuclear Fuels Room: Capitol Hill


08:30-08:55 [O2.31]

Property evolutions of

neutron-irradiated Ti-Si-

C and Ti-Al-C MAX-

phase materials

Y. Katoh*1, C. Ang1, P.

Edmondson1, C. Shih1, C.

Parish1, M. Tunes2, 1Oak

Ridge National

Laboratory, USA,

2University of

Huddersfield, UK

[O4.28]

Numerical and analytical

modelling in support of

miniaturized mechanical

testing and micromechanical

property evaluation

P. Hähner*1, A. Ruiz Moreno1,

C. Soyarslan2, B. Gülçimen

Çakan3, S. Bargmann2, 1Joint

Research Centre, The

Netherlands, 2University of

Wuppertal, Germany,

3Uludag University, Turkey

[O7.31]

Direct observation of fission

product noble metal phase

particles in the UO2 nuclear

fuel - Zr cladding interaction

region in high burn-up spent

nuclear fuel

T.G. Lach*, E.G. Buck, B.K.

McNamara, M.A. Conroy,

J.M. Schwantes, R.

Clark, Pacific Northwest


[O6.17]

Comparison of

microstructural

development between Fe-

12Cr and Fe-12Cr-5Al under

irradiation

N. Hashimoto*1, K. Toyota1,

Y. Tang1, K. Sakamoto2, S.

Yamashita3, 1Hokkaido

University, Japan, 2Nippon

Nuclear Fuel Development,

Japan, 3Japan Atomic

Energy Agency, Japan

[O5.19]

Advanced

mechanical testing of

accident-tolerant fuel

cladding tubes

M.N. Cinbiz*, M. Gussev, K.

Linton, K. Terrani, M. Howell,

R. Lowden, Oak Ridge


[O3.24]

Development of a layered

two-dimensional approach

for modelling fuel rod

behaviour

K.A. Gamble*,

G. Pastore, Idaho National

Laboratory, USA

08:55-09:20 [O2.32]

Understanding the role of

niobium on the hydrogen

uptake mechanism of

zirconium alloys in

primary water

B. Queylat*1, M. Jublot1, F.

Martin2, N. Bendib1, F.

Miserque2, P. Bossis2, M.

Tupin1, 1CEA-DEN, France,

2Université Paris-Saclay,

France

[O4.29] Effects of uniaxial stress on 1D migrating self-interstitial clusters in production bias method

S.I. Choi*1, M.J.

Banisalman2, J.H.

Kim1, 1Ulsan National

Institute of Science and

Technology, Republic of

Korea, 2Seoul National


Korea

[O7.32]

Effect of Mo presence on

the Cs migration in UOx

C. Panetier*1, Y. Pipon1 ,2, C.

Gaillard1, N. Moncoffre1, L.

Sarrasin1, D. Mangin3, P.

Sainsot4, R. Ducher5, R.

Dubourg5, 1UCBL,

CNRS/IN2P3, IPNL, France,

2UCBL, IUT Lyon 1, France,

3IJL Université de Lorraine,

France, 4INSA Lyon, France,

5IRSN, France

[O6.18]

Influence of the

microstructure on the void

swelling of a 6061 aluminum

alloy under irradiation

V. Garric*1, P. Donnadieu2,

G. Renou2, B.

Kapusta1, 1DEN-Service

d’Etudes des Matériaux

Irradiés, CEA Université Paris-

Saclay, France, 2University

Grenoble Alpes, France

[O5.20]

Advances in performance

and manufacturing of SiC-

SiC composite accident

tolerant fuel cladding

H.E. Khalifa*1, C.P. Deck1,

G.M. Jacobsen1, J.

Sheeder1, S. Oswald1, K.

Shapovalov1, E. Song1, S.

Gonderman1, R.

Haefelfinger1, J.

Gazza1, 1General Atomics,

USA, 2Westinghouse Electric

Company LLC, USA

[O3.25]

Effects of Cr dopants on

generalized stacking fault

energies in UO2 by means

of molecular dynamics

simulations

R.A. Ngayam-Happy*, M.

Kosa, M. Krack, Paul

Scherrer Institut, Switzerland

09:20-09:45 [O2.33]

A tomographic TEM

[O4.30]

Dislocation bias and sink

[O7.33]

Anisotropic mechanical [O6.19] Effect of helium on

[O5.21]

Micromechanical [O3.26]

Combining cluster


study of dislocation slip

structures in pure

zirconium

Q. Wang*1, F. Long1, J.

Kacher2, Z. Yao1, M.R.

Daymond1, 1Queen's

University, Canada,

2Georgia Institute of

Technology, USA

strength in bcc Fe based on

mesoscale defect dynamics

H. Xu, The University of

Tennessee, USA

response of depleted

uranium single crystal

micro-pillar

P. Zhou*1, R.W. Li2, D.W.

Xiao2, C. Lu2, Y. Hu1, L.F.

He2, 1Science and

Technology on Surface

Physics and Chemistry

Laboratory, China,

2Insititute of Materials,

China Academy of

Engineering Physics

(CAEP), China

dislocation and cavity

evolution in neutron

irradiated TMS and ODS

ferritic alloys

H.J. Jung1, D.J.

Edwards*2, K.

Kruska2, R. Kurtz2, T.

Yamamoto3, Y. Wu3,

G.R.

Odette3, 1Northwes

tion University, USA,

2Pacific Northwest

National

Laboratory, USA,

3University of

California-Santa

Barbara, USA

characterization of the

radiation and temperature

effects on SiC-SiC fiber

composites for accident-

tolerant fuel applications

Y. Zayachuk*1, A. Hussey1,

D.E.J. Armstrong1, C. Deck2,

P. Hosemann3, 1University of

Oxford, UK, 2General

Atomic, USA, 3University of

California, USA

expansion and first-

principles calculations to

study the USi-USi2 pseudo-

binary phase space

V. Kocevski*, T.M.

Besmann, University of

South Carolina, USA



Fission and Fusion

reactors

Room: Seattle 1 Session Chair: S.S. Raiman



Nuclear Fuels

Room: Seattle 3

Session Chairs: T. Lach,

J. Wharry




Room: Belltown



Track 5 Continued

Room: Pioneer

Session Chair: M.K. Grosse

Track 3 Continued

Room: Capitol Hill


09:45-10:10 [O2.34]

Crystal orientation

dependence of

irradiation-induced

hardening in Zr-Nb alloys

H.L. Yang*1, S. Kano1, J.

McGrady1, Y.

Matsukawa2, D.Y. Chen1,

K. Murakami3, H.

Abe1, 1The University of

Tokyo, Japan, 2Tohoku

University, Japan,

3Nagaoka University of

Technology, Japan

[O7.34]

Non-destructive

characterization of hydrided

Zr and Zircaloy-4 cladding

by neutron radiography and

tomography B. Beers*1, H. Bilheux2, Y.

Yan2, B. Heuser2, 1University

of Tennessee - Knoxville,

USA, 2Oak Ridge National

Laboratory, USA

[O6.20]

Irradiation effects in high

entropy alloys

W-Y. Chen*1, Y. Chen1, X.

Liu2, J-W. Yeh3, K-K. Tseng3,

K. Natesan1, 1Argonne


2University of Illinois, USA,

3National Tsing Hua

University, Taiwan

[O5.22]

Hermeticity evaluation of

SiC/SiC composite tubes

relevant to LWR cladding

application

X. Hu*, T. Koyanagi, G.P.

Singh, C.M. Petrie, Y.

Katoh, Oak Ridge National

Laboratory, USA

[O3.27]

Development of a thermal

resistor model and

microstructure design tool for

UO2 composite fuels

F.W. Hilty*, M.R.

Tonks, University of Florida,

USA


Room: Seattle 1-3

10:40-11:20 [L02] - Best Paper Award Presentation

Microstructure characterization and strengthening mechanisms of oxide dispersion strengthened (ODS) Fe-9%Cr and Fe-14%Cr extruded bars

A. Chauhan, Karlsruhe Institute of Technology, Germany

11:20-12:00 [PS7]

Structural material options for Gen IV and fusion energy systems

P. Yvon, Commissariat à l'énergie atomique et aux énergies alternatives, France

12:00-12:40 [PS8]

Recent advancements in multi-scale fuel modelling techniques

C. Stanek, Los Alamos National Laboratory, USA

12:40-13:10 NuMart Awards/Best Poster Awards/Young Researcher Awards/Closing Ceremony


End of Conference

Documents

Oral Program - elsevier.com · Armstrong, A.J. Wilkinson, University of Oxford, UK [O4.02] Phosphorous effect on vacancy-mediated diffusion and ordering kinetics in nickel alloys